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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
A. Klix, P. Batistoni, U. Fischer, H. Freiesleben, D. Leichtle, K. Seidel, S. Unholzer
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 776-780
Technical Paper | Nuclear Analysis and Experiments | doi.org/10.13182/FST07-A1584
Articles are hosted by Taylor and Francis Online.
A mock-up of the European Helium-Cooled Pebble Bed TBM was irradiated with DT neutrons in pulsed and continuous mode at the Fusion Neutronics Laboratory of the University of Technology Dresden. The aim was to measure fast neutron and gamma-ray flux spectra as well as time-of-arrival spectra of the slow neutron flux. The results of the experiments were analysed by the Monte Carlo code MCNP and nuclear data from the European Fusion File (EFF-3),and the Fusion Evaluated Nuclear Data Library (FENDL-2.0/2.1). It was found that the calculation of the fast neutron flux above 3 MeV tends to overestimate while the gamma-ray flux and slow neutron flux in two measurement positions in the mock-up was underestimated. The mock-up was also irradiated at FNG/ENEA Frascati to measure tritium breeding rates by means of small Li2CO3 pellet detectors inserted into the breeding layers. The breeding experiment was analysed at FZ Karlsruhe with emphasis on determining sensitivities of the TPR to relevant cross section uncertainties of all materials in the mock-up. It was found that the TPR calculation shows a tendency to underestimate. From the sensitivity analysis it was found that the total TPR is most sensitive to the elastic scattering in Be and the 7Li(n,T) reaction.